ML20045D183

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Forwards Rev to TS Section 6.9.1.8,providing Clarification Re Radioactive Effluent Release Rept Frequency,Per Util 930301 Ltr & Subsequent Conversations W/Nrc
ML20045D183
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/16/1993
From: Fenech R
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045D184 List:
References
93-01, 93-1, NUDOCS 9306280071
Download: ML20045D183 (2)


Text

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l i

Tennessee Vafley Authonty, Pont Office Box 2000. Soddy-Daisy, Tennessee 37379-2000 i

l Robert A. Fenech Vice President Sequoyah Nuclear Plant June 16, 1993 TVA-SQN-TS-93-01 10 CFR 50.90

  • U.S. Nuclear Regulatory Commission ATTN: Document Control Desk l Washington, D.C. 20555 Gentlemen:

In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - UPDATED INFORMATION TO TECHNICAL SPECIFICATION (TS) CHANGE 93-01, " REVISION OF RADIOACTIVE EFFLUENT RELEASE REPORT FREQUENCY"

Reference:

TVA letter to NRC dated March 1, 1993, " Technical Specification (TS) 93-01, ' Revision of Radioactive Effluent Release Report Frequency'"

The above reference requested a revision to the TSs in regard to the frequency for submitting the effluent release report in accordance with 10 CFR 50.36a(a)(2). Subsequent conversations with NRC have clarified the NRC requirements. Specifically, the effluent release report content is to be based on calendar activities while the submittal of the report j is to occur before a specific milestone, consistent with other reports required by the TSs.

It is our understanding that this clarification is to be provided in a pending generic letter that will suggest a milestone date of May 1 for submittal of the report.

Accordingly, TVA is providing a revised requested change to TS Section 6.9.1.8 for Units 1 and 2. These revised pages are provided in the attached enclosure and replace those previously provided in the above reference with regard to TS Section 6.9.1.8 only. The no significant hazard evaluation provided in Enclosure 3 of the above reference is not affected by this proposed revision. The reason and justification for this revision are as described above.

'/90023 g 9306280071 930616 PDR P

ADOCK 05000.?27 g PDR

I U.S. Nuclear Regulatory Comission ,

Page 2 l June 16, 1993 l Please direct questions concerning this issue to D. V. Goodin at l (615) 843-7734.

Sincerely, hb $-

Robert A. Fenech Sworn to and subscr ed before me this M day of _ 1993 m E (L B L ~ Jo Notary Publ'ic My Comission Expires 9!77 Enclosure cc (Enclosure):

Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Comission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director (w/o Enclosures)

Division of Radiological Health 3rd Floor L & C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Comission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711